ML19249D966
| ML19249D966 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/10/1979 |
| From: | Olshan L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7909250619 | |
| Download: ML19249D966 (14) | |
Text
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\\..... P' September 10, 1979 Docket No. 50-247 LICENSEE:
Consolidated Edison Company of New York FACILITY:
Indian Point, Unit No. 2 SUBJEC':
SUMMARY
OF MEETING ON SEPTEMBER 6, 1979 TO DISCUSS STEAM GENERATOR INSPECTION A meeting was held on September 6, 1979 between representatives of Consolidated Edison and the NRC staff.
A list of attendees is given in.
The meeting was requested by Consolidated Edison after they were informed that a license condition would be issued that, similar to the present license condition, would require inspection of all four steam generators within the next sixteen equivalent months of operation.
The licensee presented the material in Enclosure 2 to support the position that only two steam generators should be inspected within the next sixteen months of equivalent operation.
The benefit would be a reduction in personnel exposure, from approximately 84 man rem for inspection of four steam gen-erators to approximately 45 man rem for two steam generators.
(All four steam generators are inspected simultaneously, so halving the number of steam generators inspected would not significantly reduce the inspection time.) The licensee stated that since all four steam generators appear to be degradir.g very slowly, and at approximately the same rate, they were of the opinion the additional information gained from inspection of four steam generators would not warrant the additional exposure to personnel.
Tha NRC staff stated that in the only case where a steam generator inspection license condition had been removed, it was removed only after no further denting had been observed during two successive inspections.
Results of the inspection just completed indicated that denting in the Indian Point 2 steam generators is still progressing, and although it is progressing more slowly than at some other facilities, it still may result in leaking tubes in the future.
Further, the staff stated that if the licensee only planned inspection of two steam generators, and this inspection indicated that inspection of the other two steam generators was necessary, then outage time might be extended and there would be no reduction in personnel exposure.
Thus, the staff said it will continue to closely me.itor the licensee's steam generators, and that the amendment to be issued prior to unit start-up will require inspection of all four steam generators within sixteen equivalent months of operation.
O g, (. u L. Olshan, Project Manager Operating Reactors Branch #1
Enclosures:
As stated Division of Operating Reactors 7 9 09 25 0 $/ 9 p\\
1020 112 cc: w/ enclosures
's See next page
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William J. Cahill, Jr.
Consolidated Edison Company of New York, Inc.
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White Plains Public Library
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100 ",arti..e Avenue g
White P1 ains, New York 10601 Jose;n D. Block, Esquire Executive Vice President Administrative Consolidated Edison Company cf New York, Inc.
4 Irving Place New York, New York 10003 Charles W. Jackson Nuclear Licensing Engineer Consolidated Edison Company of New York, Inc.
4 Irving Place New York, New York 10003 Anthony Z. Roisman Natural Resources Defense Council 917 15th Street, N.W.
Washington, D. C.
20005 Dr. Lawrence R. Quarles Apartment 51 Kendal at Longwood Kennett Square, Pennsylvania 19348 Theodore A. Rebel owski U. S. Nuclear Regulatory Commission P. O. Box 38 Buchanan, New York 10511 John D. O' Tool e Assistant Vice President Consolidated Edison Company of New York, Inc.
4 Irving 91 ace New York, New York 10003 1020 113
Enclosure I LIST OF ATTENDEES CONSOLIDATED EDIS0N NRC W. Bennett B. D. Liaw L. Liberatori E. Murphy S. Rothstein V. Noonan
- L. Olshan J. Strosnider
- Part-time Attendance
'[t 1020 114
4 a
Meeting Summary for Indian Point, Unit No. 2
)
g Docket Files NRC PDR Local PDR ORB 1 Reading NRR Reading H. Denton E. Case D. Ei senhut G. Zech B. Grimes W. Gammill L. Shao J. Miller R. Vollmer T. J. Carter A. Schwencer D. Ziemann P. Check G. Lainas D. Davis B. Grimes T. Ippolito R. Reid V. Noonan D. Crutchfield G. Knighton D. Brinkman Project Manager OELD 01&E (3)
C. Parrish/P. Kreutzer ACRS (16)
NRC Participants J. Buchanan
+-==i+=-
TERA #
Licensee Short Service List 1020 O
STEAM GENERATOR PROGRAM 1979 REFUELING OUTAGE
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O M
9 N0 INSERVICE LEAKS NOVEMBER 1976 TO CURRENT UUNE 1979) 6 O
O N
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STEAM GENERATOR PROGRAM e EDDY CURRENT FOR TUBE DEFECTS AND DENTS e VISUAL FOR SUPPORT PLATE CONDITION e SLUDGE ANALYSIS M
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G D
E
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M A
X S
E TC S
E E
F B
E U
D T
E 0
B 0
U 5
1 T
O X
N O
R P
P A
e W
M OO w
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APPROXIMATE EXPOSURE - ECT '79 Eddy Current Personnel 23 men 21 Man Rem (7)1200ea)
PGM - Water Box Entries 21 men 38 Man Rem (1500-2200ea)
PGM - Misc 13 men 20 Man Rem PGM Foremen 10 men 5 Man Rem (estimated exposure) 84 Man Rem a
CD
EDDY CURRENT EXAMINATION FOR TUBE DEFECTS AND DENT SG 21 440 TUBES SG 22 389 TUBES SG 23 289 TUBES SG 24 401 TUBES 1,519 TUBES 5
E8 R
DENT MEASUREMENTS (MILS)
JULY 1979 MARCH 1978 JUNE 1976 AVG.
MAX.
AV G.
MAX.
AVG.
MAX 5G 23
- 2. 7 15
- 2. 6 9
4.3 12 24 2.3.
9
- 2. 2 9
3.4 10 N
CD N
DENT MEASUREMENTS (MILS)
JULY 1979 APRIL 1977 JUNE 1976 AV G.
MAX.
AVG.
MAX AVG.
MAX.
SG 21 3.1 13 3.0 20 4.2 15 SG 22 2.4 9
2.7 10 2.7 9
R u
i Comoa ri son o f Exami nat ion Results for '79 S.G.
21 S.G.
22 Item S.G.
23 S.G.
24 649.5 EPPD since last exam
'39.2 Critical Days since 357 701 last exam o
o Defects o
o 25.5%
19.5%
Restricted to 700 mil 23.5%
2 6. 7','
2.7%
2.3%
Restricted to 610 mil 2.1%
1.3%
3 tubes 8 tubes Restricted to 610 mil 6 tubeg 5 tubes o
o Restricted to 540 mil o
1 N
CD 4
e o
e F
ONE 1JBE DID NOT PASS 540 PROBE APPROX.1500 TUBES EXAMINED M
N CD N
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